Inert matrix fuel performance during the first two irradiation cycles in a test reactor: comparison with modelling results

2003 ◽  
Vol 319 ◽  
pp. 87-94 ◽  
Author(s):  
Ch. Hellwig ◽  
U. Kasemeyer
2006 ◽  
Vol 48 (6) ◽  
pp. 590-598 ◽  
Author(s):  
N. Kamel ◽  
H. Aït-Amar ◽  
Z. Kamel ◽  
N. Souami ◽  
S. Telmoune ◽  
...  

1998 ◽  
Vol 540 ◽  
Author(s):  
C. Degueldre ◽  
M. Pouchon ◽  
M. Doebli ◽  
G. Ledergerber

AbstractA zirconia based ceramic is foreseen as an inert matrix fuel for burning excess plutonium in light water nuclear reactors. For reactor safety reasons the behaviour of volatile fission products such as cesium and iodine must be studied since a retention of fission products is favourable for licensing the studied inert matrix fuel. In this study, implantation of Cs and I was performed into polycrystalline (Zr0.85, Y0.15)O1.925 samples. The implantation depth was selected on the basis of the ability to observe by Rutherford backscattering spectroscopy (RBS) the behaviour of Cs and I after treatment. With a 1 MeV incident energy, the ions are implanted at a depth of 200 nm as predicted by TRIM. After implantations full quantification of I and Cs concentration profiles was performed by RBS. The implantation profiles are measured as a function of sample temperature during stepwise heating programs. It is interesting to observe retention of Cs and I at relatively high temperature (e.g. for 2 h, below 900 K for Cs and below 1400 K for I). This behaviour is likely to be due to the size and interactions of these species in the zirconia solid solution.


2006 ◽  
Vol 352 (1-3) ◽  
pp. 291-299 ◽  
Author(s):  
Ch. Hellwig ◽  
M. Streit ◽  
P. Blair ◽  
T. Tverberg ◽  
F.C. Klaassen ◽  
...  

2003 ◽  
Vol 319 ◽  
pp. 37-43 ◽  
Author(s):  
M.A. Pouchon ◽  
M. Nakamura ◽  
Ch. Hellwig ◽  
F. Ingold ◽  
C. Degueldre

2009 ◽  
Vol 1215 ◽  
Author(s):  
Ting Cheng ◽  
Ronald Baney ◽  
James Tulenko

AbstractSilicon carbide is one of the prime matrix material candidates for inert matrix fuels (IMF) which are being designed to reduce plutonium and long half-life actinide inventories through transmutation. Since complete transmutation is impractical in a single in-core run, reprocessing the inert matrix fuels becomes necessary. The current reprocessing techniques of many inert matrix materials involve dissolution of spent fuels in acidic aqueous solutions. However, SiC cannot be dissolved by that process. Thus, new reprocessing techniques are required.This paper discusses a possible way for separating transuranic (actinide) species from a bulk silicon carbide (SiC) matrix utilizing molten carbonates. Bulk reaction-bonded SiC and SiC powder (1 μm) were corroded at high temperatures (above 850 °C) in molten carbonates (K2CO3 and Na2CO3) in an air atmosphere to form water soluble silicates. Separation of Ceria (used as a surrogate for the plutonium fissile fuel) was achieved by dissolving the silicates in boiling water and leaving behind the solid ceria (CeO2).


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